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Preliminary Studies of the Adsorption of Uranium in a Resin-In-Pulp System

Description: Data were obtained in non-flowing and flowing (continuous) batch adsorption systems to serve as a guide to the operating conditions that should be used in a resin-in-pulp adsorption system for the recovery of uranium from ores.
Date: July 27, 1953
Creator: Abrams, Charles S. & Kaufman, David
Partner: UNT Libraries Government Documents Department
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Experimental Determination of Contact Conductance for Some Stainless Steel Contacts

Description: "Contact conductances for three semi-smooth and rough stainless steel contacts involving six steels are determined. The procedure and equipment used are fully described, and the results are given. Graphs display thermal conductance and conductivity versus pressure and temperature."
Date: July 1962
Creator: Adamantiades, Achilles
Partner: UNT Libraries Government Documents Department
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Stability of Florothene Under Exposure to Gamma Radiation

Description: The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.
Date: July 6, 1956
Creator: Adler, K. L.
Partner: UNT Libraries Government Documents Department
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Program Study Report Plutonium Fuel Cycle

Description: From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date: July 30, 1956
Creator: Albaugh, F. W. & Fryar, R. M.
Partner: UNT Libraries Government Documents Department
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The Effect of Radiation on the Corrosion of Metals by Water

Description: Technical report. Long-time tests have been made on the effect of various types of radiation on the corrosion of 2S aluminum in simulated W water. In no case was any acceleration of corrosion by the radiation observed; the effect of radiation, if any, appeared to be a protective one. Deuteron irradiation did accelerate the corrosion of mild steel at low flow rates in hot water of pH 6 to 7, but no appreciable effect was observed with copper, stainless steel, or tuballoy. The general theory … more
Date: July 6, 1944
Creator: Allen, A. O. (Augustine O.); Bowman, M. C.; Goldowski, Nathalie; Larson, R. G. & Treiman, L.
Partner: UNT Libraries Government Documents Department
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X-Ray Fluorescence Tables: Program Description

Description: Report discussing the mechanics of X-Ray and COMBO computer programs.
Date: July 20, 1964
Creator: Amsbury, W. P.; Lee, W. W.; Rowan, J. H. & Walden, G. E.
Partner: UNT Libraries Government Documents Department
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Acute Radiotoxicity of Injected Yttrium91

Description: Report describing results of experiments that involved injecting radioactive yttrium into animals: "The excretion, retention, and distribution of the yttrium was measured, and its effect on survival and growth was observed. The average total excretion of Y91 to the time of death (from 76 hours to 24 days) was a little less than 30 per cent of the injected dose" (p. 2).
Date: July 31, 1947
Creator: Anthony, David S.
Partner: UNT Libraries Government Documents Department
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Measurements on the Environmental Radioactivity in India from Nuclear Weapon Tests. Data Collected During 1956-61

Description: In this report the data on the measurements of radio activity of air, rainwater, milk and a variety of food samples is tabulated. A brief outline of the sampling and counting procedures is also given. Interpretation and discussion of the results as well as further details of the methods of sampling and counting have already been given in the various reports published by this section. A bibliography of those reports is given at the end.
Date: July 1962
Creator: Atomic Energy Establishment (India)
Partner: UNT Libraries Government Documents Department
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K [infinity] in Uranium - Water Lattices

Description: This report follows experiments on K[infinity], measuring the element for several red sizes, enrichments, and water-to-uranium volume ratios-(1, 2), by making use of the relation k[infinity] = 0M-[2]B-[2] (M-2 = migration area, B = buckling). The purpose of this report is to compare the experimental data for k[infinity] with values calculated from the four-factor formula k[infinity] = [eta][epsilon]pf.
Date: July 28, 1955
Creator: Auerback, T.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: July 15, 1964
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: July, 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this months report includes specifications a utility loop, further calculations for fuel rods, drawings were reviewed and specifications for the core reactor were reviewed.
Date: July 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment: Quarterly Technical Report No. 1, BAW-1001, July 1, 1956 to November 15, 1956

Description: This is the first quarterly report which summarizes the project work on the Liquid Metal Fuel Reactor Experiment. As the initial contract was not signed until November, 1956, progress within this reporting period has been limited to establishing objectives, determining what research and development will be required, and selecting preliminary design parameters.
Date: 1956-07/1956-11
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report: Babcock & Wilcox Test Reactor

Description: This preliminary Hazards Summary Report presents to the Atomic Energy Commission (AEC), Division of Licensing and Regulation, a description of the Nuclear Development Center, the characteristics of the proposed site, and an evaluation of the potential hazards associated with operating the test reactor at this location.
Date: July 1962
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Maximum Allowable Concentration for Air-Borne Beta Contamination

Description: The following report discusses an equation derived by which the maximum allowable concentration in the atmosphere of a beta-omitting isotope for which lung damage is the limiting consideration can be calculated.
Date: July 5, 1951
Creator: Bailey, J. C. & Henry, H. F.
Partner: UNT Libraries Government Documents Department
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A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures

Description: Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Partner: UNT Libraries Government Documents Department
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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins

Description: This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases
Date: July 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Final Report : Large Reactor Study for Sea Water Distillation

Description: From introduction: This report presents the results of a study of large nuclear reactor systems for supplying energy for the distillation of sea water.
Date: July 1963
Creator: Bechtel Corporation
Partner: UNT Libraries Government Documents Department
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